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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20249C1601998-06-24024 June 1998 Transmits Revised Fda for Sys 80+ Design,Per App O of 10CFR52.Duration of Fda Conforms W/Duration of Design Certification Rule for Sys 80+ Std Design LD-98-009, Forwards 3 Copies of Amend X to CESSAR-Design Certification (DC) Sys 80+ Std Plant Ssar Which Is Reprint of CESSAR-DC That Incorporates Revs Made to Approved Design Matl in Dcd. All CESSAR-DC Pages Designated Except for Listed Info1998-03-13013 March 1998 Forwards 3 Copies of Amend X to CESSAR-Design Certification (DC) Sys 80+ Std Plant Ssar Which Is Reprint of CESSAR-DC That Incorporates Revs Made to Approved Design Matl in Dcd. All CESSAR-DC Pages Designated Except for Listed Info ML20203J3231997-12-17017 December 1997 First Partial Response to FOIA Request for Documents.Records in App a & B Encl & Will Be Available in PDR ML20149J7101997-07-23023 July 1997 Requests That R Simard Be Removed from Service Lists & R Bell Be Added to Svc Lists,Due to Recent NEI Reorganization LD-97-020, Requests That Errata Be Corrected in Errata Amend to Sys 80+ Design Certification Rule.Memo from Egan & Assoc to C Brinkman Which Lists Errata,Basis for Correction & Suggested Corrections Encl1997-06-13013 June 1997 Requests That Errata Be Corrected in Errata Amend to Sys 80+ Design Certification Rule.Memo from Egan & Assoc to C Brinkman Which Lists Errata,Basis for Correction & Suggested Corrections Encl LD-97-015, Informs That ABB-CE Has Completed Review of Effective Page Listing & Sys 80+ Design Control Document Revs Dtd Jan 19971997-05-0707 May 1997 Informs That ABB-CE Has Completed Review of Effective Page Listing & Sys 80+ Design Control Document Revs Dtd Jan 1997 LD-97-014, Transmits Final Version of Sys 80+ Design Control Document (DCD)1997-04-30030 April 1997 Transmits Final Version of Sys 80+ Design Control Document (DCD) ML20138E0301997-04-25025 April 1997 Informs That Portion of Info in Encl 1 of Vendor 960416 Submittal of Presentation Matl on ABB-C-E Licensing Plan for Full Batch Implementation of Abb Advanced Fuel for Meeting Held on 960416 W/Nrc Will Be Withheld,Per 10CFR2.790 ML20147C0881997-01-23023 January 1997 Responds to Requesting Opportunity to Review Design Certification Rule for Abb Combustion Engineering Sys 80+ Before Sending to Office of Fr for Publication ML20133A9791996-12-18018 December 1996 Approves Rules Certifying Asea Brown Boveri-Combustion Engineering Sys 80+ & General Electric Nuclear Energy Advanced Boiling Water Reactor ML20133A9811996-12-18018 December 1996 Informs That NRC Has Approved Rules Certifying Two Evolutionary Reactor Designs:Asea Brown Boveri-Combustion Engineering Sys 80+ & GE Nuclear Energy ABWR ML20133A9871996-12-18018 December 1996 Informs of NRC Approval of Rules Certifying Two Evolutionary Reactor Designs,Asea Brown Boveri-CE Sys 80+ & GE Nuclear Energy ABWR ML20133A9901996-12-18018 December 1996 Informs That NRC Has Approved Asea Brown Boveri CE Sys 80+ & GE Nuclear Energy ABWR as Evolutionary Reactor Designs ML20133B0191996-12-18018 December 1996 Informs of Approval of Rules Certifying Two Evolutionary Reactor Designs,Asea Brown Boveri-Combustion Engineering Sys 80+ & GE Nuclear Energys Advanced BWR LD-96-062, Requests Authorization to Conduct Narrowly,Focused Review of Design Certification Rule for Sys 80+ Before Sending of Office of Fr for Publication1996-12-18018 December 1996 Requests Authorization to Conduct Narrowly,Focused Review of Design Certification Rule for Sys 80+ Before Sending of Office of Fr for Publication LD-96-060, Forwards Rev to Sys 80+ Std Plant Design Control Document1996-12-13013 December 1996 Forwards Rev to Sys 80+ Std Plant Design Control Document ML20149M3091996-12-10010 December 1996 Responds to Which Requested Status of CESSAR-DC Relative to Fda for Sys 80+ Design ML20129E7111996-10-0101 October 1996 Forward RAI Re CENPD-137,Suppl 2-P, Calculative Methods for Abb CE Small Break LOCA Evaluation Model. Submittal Being Withheld from Public Disclosure Pending Staff Final Determination,Per 960523 Request LD-96-042, Submits Misleading Statement by BNL on C-E Reactor Coolant Pump Seals.Statement Correction Listed1996-09-26026 September 1996 Submits Misleading Statement by BNL on C-E Reactor Coolant Pump Seals.Statement Correction Listed ML20128P4981996-09-23023 September 1996 Forwards Proposed Rule Language for 3 Design Certifications Discussed at 960827 NRC Briefing ML20128N6001996-09-16016 September 1996 Provides Addl Info in Response to Several Questions Raised by Commission During 960827 Briefing on Design Certification Rulemaking LD-96-029, Forwards Finalized Package of Six Draft Changes to Sys 80+ Std Plant Design Control Document.Changes Will Be Formally Incorporated Into Sys 80+ Design Control Document at Conclusion of Design Certification Rulemaking1996-07-25025 July 1996 Forwards Finalized Package of Six Draft Changes to Sys 80+ Std Plant Design Control Document.Changes Will Be Formally Incorporated Into Sys 80+ Design Control Document at Conclusion of Design Certification Rulemaking LD-96-028, Submits Addl Draft Changes for Staff Review & Approval. Changes Listed on Attached Table W/Details Shown on Encl Design Control Document Pages1996-07-17017 July 1996 Submits Addl Draft Changes for Staff Review & Approval. Changes Listed on Attached Table W/Details Shown on Encl Design Control Document Pages LD-96-024, Transmits Finalized Package of Changes to Sys 80+ Std Plant Design Control Document1996-06-27027 June 1996 Transmits Finalized Package of Changes to Sys 80+ Std Plant Design Control Document LD-96-021, Submits Changes to Sys 80+ Std Plant Design Control Document as Requested by for Staff Review & Approval1996-06-11011 June 1996 Submits Changes to Sys 80+ Std Plant Design Control Document as Requested by for Staff Review & Approval ML20107G1451996-04-17017 April 1996 Transmits CEOG Task 931 Survey Questionnaire-CEA Insertion Experience W/High Burnup Fuel Mgt ML20101P1231996-03-15015 March 1996 Expresses Appreciation for Opportunity on 960308 to Brief Commission on Views on Design Certification Rules, Particularly W/Respect to Issue of Applicable Regulations LD-95-026, Requests Addl Explanation of Probablistic Risk Assessment. Request for Clarification & Does Not Impact Conclusions of Evaluation Already Reported in FSER1995-10-0606 October 1995 Requests Addl Explanation of Probablistic Risk Assessment. Request for Clarification & Does Not Impact Conclusions of Evaluation Already Reported in FSER LD-95-040, Forwards ABB-CE Proposed Statement of Considerations to Accompany ABB-CE Proposed Rule,Presented in Form of Complete Rulemaking Package1995-09-0505 September 1995 Forwards ABB-CE Proposed Statement of Considerations to Accompany ABB-CE Proposed Rule,Presented in Form of Complete Rulemaking Package ML20092D2561995-08-23023 August 1995 Forwards Correction to Comment 20 Re Proposed Design Certification Rules for Standardized Advancement Reactors. Last Line of Text May Have Been Lost Due to Word Processing Error ML20092D2871995-08-23023 August 1995 Forwards Correction to Comment 19 Re Proposed Design Certification Rules for Standardized Advanced Reactors. Last Line on First Page May Have Been Lost Due to Word Processing Error ML20085G2711995-06-14014 June 1995 Proposes to Respond to RAIs on GE TR NEDE-32177P, Tracg Computer Code Qualification, Dtd Jan 1993 in Three Groups as Indicated in Attachment ML20082G5511995-04-10010 April 1995 Provides Documents & Info Requested in NRC Audit (950407- 950410) Re Rv Fabrication ML20203J4371995-04-0404 April 1995 Forwards Fr Notice Re Proposed Amends to Commission Regulations for Commercial Npps,Adding New App a to 10CFR52 Which Will When Promulgated Certify Sys 80+ Std Design of ABWR LD-95-015, Transmits Corrected Page for Incorporation Into Sys 80+ DCD Revs1995-03-27027 March 1995 Transmits Corrected Page for Incorporation Into Sys 80+ DCD Revs LD-95-013, Transmits Supplementary Revs for Incorporation Into DCD & Affidavit.Changes Resolve Inconsistencies Identified by NRC & by ABB-CE1995-03-24024 March 1995 Transmits Supplementary Revs for Incorporation Into DCD & Affidavit.Changes Resolve Inconsistencies Identified by NRC & by ABB-CE LD-95-011, Forwards Rev Pages for Sys 80+ Design Control Document. Margin Bar Adjacent to Change & Rev Date Will Be Added to Revised DCD Page1995-03-17017 March 1995 Forwards Rev Pages for Sys 80+ Design Control Document. Margin Bar Adjacent to Change & Rev Date Will Be Added to Revised DCD Page LD-95-003, Provides Addl Info on Removal of Auxiliary Throttle Seal Coolers from Reactor Coolant Pumps,In Response to NRC Questions from Review of Sys 80+ Design Control Document1995-03-0303 March 1995 Provides Addl Info on Removal of Auxiliary Throttle Seal Coolers from Reactor Coolant Pumps,In Response to NRC Questions from Review of Sys 80+ Design Control Document LD-95-007, Forwards Revised Sys 80+ Design Control Document1995-02-22022 February 1995 Forwards Revised Sys 80+ Design Control Document LD-95-006, Forwards mark-up Pages Identifying Revs Incorporated Into Sys 80+ Design Control Document. Revs Provided in Response to Comments Provided by NRC & as Result of Changes Identified by ABB-CE & Discussed W/Nrc1995-02-16016 February 1995 Forwards mark-up Pages Identifying Revs Incorporated Into Sys 80+ Design Control Document. Revs Provided in Response to Comments Provided by NRC & as Result of Changes Identified by ABB-CE & Discussed W/Nrc LD-95-001, Forwards Rev 2 to Technical Support Document for Amend to 10CFR51 Considering Severe Accident Under NEPA for Plants of Sys 80+ Design1995-01-0606 January 1995 Forwards Rev 2 to Technical Support Document for Amend to 10CFR51 Considering Severe Accident Under NEPA for Plants of Sys 80+ Design NRC-94-4383, Comments on Review of Draft NUREG-1512 for Proprietary Info1994-12-27027 December 1994 Comments on Review of Draft NUREG-1512 for Proprietary Info LD-94-072, Provides Justification for Tier 2 Seismic & Valve Testing Expirations1994-12-16016 December 1994 Provides Justification for Tier 2 Seismic & Valve Testing Expirations LD-94-073, Forwards Sys 80+ Design Control Document, Vols 1-241994-12-16016 December 1994 Forwards Sys 80+ Design Control Document, Vols 1-24 LD-94-071, Transmits Addl Input to System 80+ Design Control Document1994-12-15015 December 1994 Transmits Addl Input to System 80+ Design Control Document LD-94-069, Forwards marked-up CESSAR-DC Figure 5.1.2-2 Re Proposed Design Change to Remove RCP Seal Coolers1994-12-0808 December 1994 Forwards marked-up CESSAR-DC Figure 5.1.2-2 Re Proposed Design Change to Remove RCP Seal Coolers ML20078N8961994-12-0101 December 1994 Forwards Copy of Ltr NFBWR-94-033 ML20149H1941994-11-14014 November 1994 Responds to Indicating Concern Re Application of Set of Interrelated Elements That Defines Technical & Regulatory Aspects of design-basic Accident Source Term for Licensing of Passive Plants LD-94-065, Submits Proposed Language Related to Tier 2 for Sys 80+ Design Certification Rule1994-10-28028 October 1994 Submits Proposed Language Related to Tier 2 for Sys 80+ Design Certification Rule LD-94-063, Forwards Rev 1 of Technical Support Document for Amends to 10CFR51 Considering Severe Accidents Under NEPA for Plants of Sys 80+ Design1994-10-10010 October 1994 Forwards Rev 1 of Technical Support Document for Amends to 10CFR51 Considering Severe Accidents Under NEPA for Plants of Sys 80+ Design 1998-06-24
[Table view] Category:OUTGOING CORRESPONDENCE
MONTHYEARML20249C1601998-06-24024 June 1998 Transmits Revised Fda for Sys 80+ Design,Per App O of 10CFR52.Duration of Fda Conforms W/Duration of Design Certification Rule for Sys 80+ Std Design ML20203J3231997-12-17017 December 1997 First Partial Response to FOIA Request for Documents.Records in App a & B Encl & Will Be Available in PDR ML20138E0301997-04-25025 April 1997 Informs That Portion of Info in Encl 1 of Vendor 960416 Submittal of Presentation Matl on ABB-C-E Licensing Plan for Full Batch Implementation of Abb Advanced Fuel for Meeting Held on 960416 W/Nrc Will Be Withheld,Per 10CFR2.790 ML20147C0881997-01-23023 January 1997 Responds to Requesting Opportunity to Review Design Certification Rule for Abb Combustion Engineering Sys 80+ Before Sending to Office of Fr for Publication ML20133B0191996-12-18018 December 1996 Informs of Approval of Rules Certifying Two Evolutionary Reactor Designs,Asea Brown Boveri-Combustion Engineering Sys 80+ & GE Nuclear Energys Advanced BWR ML20133A9901996-12-18018 December 1996 Informs That NRC Has Approved Asea Brown Boveri CE Sys 80+ & GE Nuclear Energy ABWR as Evolutionary Reactor Designs ML20133A9871996-12-18018 December 1996 Informs of NRC Approval of Rules Certifying Two Evolutionary Reactor Designs,Asea Brown Boveri-CE Sys 80+ & GE Nuclear Energy ABWR ML20133A9811996-12-18018 December 1996 Informs That NRC Has Approved Rules Certifying Two Evolutionary Reactor Designs:Asea Brown Boveri-Combustion Engineering Sys 80+ & GE Nuclear Energy ABWR ML20133A9791996-12-18018 December 1996 Approves Rules Certifying Asea Brown Boveri-Combustion Engineering Sys 80+ & General Electric Nuclear Energy Advanced Boiling Water Reactor ML20149M3091996-12-10010 December 1996 Responds to Which Requested Status of CESSAR-DC Relative to Fda for Sys 80+ Design ML20129E7111996-10-0101 October 1996 Forward RAI Re CENPD-137,Suppl 2-P, Calculative Methods for Abb CE Small Break LOCA Evaluation Model. Submittal Being Withheld from Public Disclosure Pending Staff Final Determination,Per 960523 Request ML20203J4371995-04-0404 April 1995 Forwards Fr Notice Re Proposed Amends to Commission Regulations for Commercial Npps,Adding New App a to 10CFR52 Which Will When Promulgated Certify Sys 80+ Std Design of ABWR ML20149H1941994-11-14014 November 1994 Responds to Indicating Concern Re Application of Set of Interrelated Elements That Defines Technical & Regulatory Aspects of design-basic Accident Source Term for Licensing of Passive Plants ML20149F4231994-08-0505 August 1994 Updates Guidance on Preparation of Design Control Document Contained in .Requests Submittal of Listed Info,In Order to Preclude Iterations & Amends to Design Control Document ML20059F4031994-01-0707 January 1994 Comments on TS Sections 4 & 5 for Sys 80+.Markup Copy of Affected TS Encl.Responses to Comments Requested No Later than 2 Wks from Receipt of Ltr ML20058L3811993-12-0707 December 1993 Forwards Staff Comments on Markup Copy of Affected TS & Requests That Responses to Comments Be Provided No Later than Two Wks from Receipt of Ltr ML20058L2651993-12-0303 December 1993 Forwards Initial Staff Comments on ABB-CE Sys 80+ Tier 1 931020 & 1112 Submittals.Submittals Adequately Reflected Agreements Reached for Tier 1 Matl During 931004-06 Meetings.Several Open Items Remain Unresolved ML20058A0931993-11-16016 November 1993 Forwards Comments on TS for Sys 80+.Requests Responses to Comments No Later than 2 Weeks from Ltr Receipt to Maintain Review Schedules ML20059J0771993-11-0404 November 1993 Provides Update on Status of Review of Nuplex 80+ Control Complex for Sys 80+ Design Certification.Review Essentially Complete & NRC Preparing SER ML20057F8641993-10-14014 October 1993 Forwards Llnl Comments on ABB-CE Sys 80+ I&C Ts. Attachments 1 & 2 to Rept Provide Sample Definitions for Channels & Functional Tests NUREG/CR-6105, Forwards Preliminary Draft Version of NUREG/CR-6105, Human Factors Engineering Guidelines for Review of Advanced Alarm Sys & Draft of NUREG/CR-5908, Advanced Human Sys Interface Design Review Guideline1993-09-28028 September 1993 Forwards Preliminary Draft Version of NUREG/CR-6105, Human Factors Engineering Guidelines for Review of Advanced Alarm Sys & Draft of NUREG/CR-5908, Advanced Human Sys Interface Design Review Guideline ML20057A9391993-09-0202 September 1993 Forwards NRC Comments on CE Sys 80+ Tier 1 Submittals Dtd 930430,0503-08,0604,0618 & 0629 ML20056H6361993-08-26026 August 1993 Responds to Informal Inquiries from Design Certification Applicants Re Form & Content of Design Control Document. Forwards Presentation of Current Staff Views Re Document ML20056F3741993-08-12012 August 1993 Requests That ABB-CE Comprehensively & Systematically Evaluate Potential Design Alternatives Proposed to Reduce Probability of SGTR Containment Bypass Accident Sequences ML20056D9431993-07-30030 July 1993 Forwards Preliminary Comments on TS Sys 80+ (Chapter 16 CESSAR-DC) Submitted in App K.Status Sheet Also Encl ML20128G1051993-02-10010 February 1993 Discusses ITAAC Submittal for ABB-CE Sys 80+ & Provides Proposed Schedule for Review ML20127J2821993-01-15015 January 1993 Discusses Level of Design Detail for Sys 80+ Structures & Lists Expected Level of Completion ML20126G5571992-12-23023 December 1992 Forwards Request for Addl Info on CESSAR-DC,system 80+ Shutdown Risk Evaluation Rept ML20126F6021992-12-22022 December 1992 Forwards Llnl 921208 Rept Entitled, Review of CE 80+ FMEA & D&Did Analysis, to Be Discussed at 930106 Public Meeting 1998-06-24
[Table view] |
Text
August 5, 1994 l
)
l Docket No.52-002 Mr. C.B. Brinkman, Director Nuclear Systems Licensing .
Combustion Engineering, Inc. l 1000 Prospect Hill Road ;
Windsor, Connecticut 06095-0500 ;
Dear Mr. Brinkman:
f
SUBJECT:
DESIGN CONTROL DOCUMENT (DCD) PREPARATION The purpose of this letter is to update the guidance on preparation of a DCD i contained in my letter of August 26, 1993. The DCD will be referenced in the ,
proposed rule for the certification of the System 80+ design. Enclosed is ;
detailed guidance on the submittal of the DCD. The notice of proposed ;
rulemaking (NPR) for the System 80+ certification could be published in the Federal Reaister in October 1994. The DCD is required to be finalized prior to publication of the NPR. To preclude iterations and amendments to the DCD, {
please provide a submittal in early August of the following: (1) a proposed -
introduction to the DCD, (2) proposed markups to the standard safety analysis !
report (SSAR) for Tier 2* items, and (3) the proposed DCD Chapter 19, and a cross-reference showing where probabilistic risk assessment information that '
was removed from SSAR Chapter 19 has been relocated, or is already addressed, ;
in other parts of the DCD.
For planning purposes, a meeting to resolve any staff comments on these i submittals is tentatively scheduled for the first week of September. Resolu- ;
tions to staff comments would then be incorporated into a complete DCD submit- !
tal to be provided to the staff in early September 1994. The staff would then review the complete DCD, and resolve any comments with you by the end of '
September. This schedule supports the NPR publication date of October. ,
i
" hSigned l Dennis M. Crutchf ld, Associate Director !
for Advanced Reactors and License Renewal l Office of Nuclear Reactor Regulation !
Enclosure:
As stated cc w/ enclosure: ;gg gtg gENTE COPY i See next page DISTRIBUTION:
Docket File PDST R/F DCrutchfield WTravers ;
PDR RBorchardt RArchitzel PShea (2) i SMagruder MFranovich TWambach EJordan, T-4 D18 i JMoore,0-15B18jACRS(11)
\ + / A 0FC LA: OST PM:Pth $ PD t OtP Dg6AR_89 NAME PShem S r. RArt itret hardt D hi DATE 08///k 0 4 o[/ 94f 0 94 08/N94 0FFICIAL RECOR COPY I DOCUMENT NAME:/ DCD-GmD.CE l 9408100207 940005 I PDR ADOCK 05200002 A PDR
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ABB-Combustion Engineering, Inc. Docket No.52-002 cc: Mr. C. B. Brinkman, Manager Washington Nuclear Operations ABB-Combustion Engineering, Inc.
12300 Twinbrook Parkway, Suite 330 Rockville, Maryland 20852 Mr. Stanley E. Ritterbusch, Manager .
Standard Plant Licensing ABB-Combustion Engineering Post Office Box 500 )
l 1000 Prospect Hill Road I Windsor, Connecticut 06095-0500 Mr. Sterling Franks U.S. Department of Energy NE-42 Washington, D.C. 20585 Mr. Steve Goldberg Budget Examiner 725 17th Street, N.W.
Washington, D.C. 20503 Mr. Joseph R. Egan, Esquire Egan & Associates, P.C.
2300 N Street, N.W., Suite 600 Washington, D.C. 20037-1128 Dr. Regis A. Matzie, Vice President Nuclear Systems Development l ABB-Combustion Engineering, Inc. I Post Office Box 500 l 1000 Prospect Hill Road )
Windsor, Connecticut 06095-0500 i Mr. Ernest L. Blake, Jr.
Shaw, Pittman, Potts & Trowbridge 2300 N Street, N.W.
Washington, D.C. 20037 Mr. Ronald Simard, Director Advanced Reactor Programs Nuclear Energy Institute 1776 I Street, N.V., Suite 400 Washington, D.C. 20006-3708 i i
1
t GUIDANCE ON THE SUBMITTAL OF A DESIGN CONTROL DOCUMENT (DCD) .
This guidance is based on the goal of minimizing any differences between the ,
standard safety analysis report (SSAR) and the DCD for a design. l
- 1. References ;
References to external documents (outside the SSAR), as well as internal cross-references to other parts of the SSAR, should be retained in the ;
DCD without changes. This includes references to information deleted for purposes of DCD preparation. The NRC's views on the treatment of references in a DCD was provided in a letter from Dennis M. Crutchfield, NRC, to Joe Colvin, Nuclear Energy Institute, of May 3, 1994.
- 2. Tier 2* ,
The DCD should designate clearly (shaded, italicized, etc.) in the approved design material (Tier 2 portion of the DCD) what information is Tier 2*, A statement may be added to each Tier 2* area or in the introductory section indicating that prior NRC review and approval is required to change the information.
- 3. Combined License (COL) Action Items COL action items should be retained in the DCD without changes. An l appropriate discussion on the status of these items may be included in !
the introduction to the DCD. The discussion should state that COL action items are not requirements in and of themselves, but must be '
addressed in a COL application. The discussion should note that some action items include only high level discussion of what issues must be ,
addressed, and do not include all details of what must be addressed.
Also, the discussion should note that some COL action items do include a '
detailed discussion of what must be addressed.
- 4. Proprietary information Because of the requirements of the Federal Reaister, there should be no ,
proprietary information in the DCD. The introduction to the DCD should state that the proprietary information that is removed must be submitted as part of a COL application. To ensure that it is clear what is required for a COL application, the DCD should indicate that any de-letions of proprietary information were for purposes of DCD preparation.
- 5. Chapter 19/Probabilistic Risk Assessment (PRA) ;
- a. PRA was used in the rc<iew of the design to determine the risk significance of key structures, systems, and components. However, the details of the PRA data analysis are not required for the DCD.
Instead, an updated PRA or supplemental PRA analyses should be submitted as part of a COL application. Therefore, detailed discus-sions of PRA data analysis may be removed, but PRA insights and .
assumptions should be retained. Any information that was deleted ,
should indicate that it was deleted fro 'ie DCD, and is contained Enclosure
I I 2 in the SSAR. Severe accident and shutdown risk discussions ;
should remain in the DCD, although these may be edited to remove detailed PRA data analysis. This is consistent with the indus- :
try proposal contained in a letter from Raymond Ng, NUMARC, to l Dennis M. Crutchfield, NRC, of February 1,1994. :
i
- b. The PRA analyses in SSAR Chapter 19 discussing why various design :
features are important should be retained in the DCD. These analy- '
ses should be retcined either in Chapter 19 or the appropriate sections of the DCD discussing the systems of the design. Also, ,
SSAR internal references to other parts of the SSAR and SSAR exter- '
nal references to other documents should be retained in the DCD if they support the information retained in the DCD. *
- c. Cross-references in SSAR Chapter 19 showing where design features from key integrated plant safety analyses were incorporated into the design should be retained in the DCD in the same form as in the SSAR. Cross-references to the appropriate sections of the SSAR and certified design material (CDM) should be retained. ;
- d. Information that is currently in SSAR Chapter 19 that does not t involve PRA should be retained in the DCD. This includes addressal of items such as 10 CFR 50.34(f) items, including design alterna-tives for severe accidents required by 50.34(f)(1)(i), and Unre-solved and Generic Safety Issues (USIs/GSIs).
- 6. Conceptual Design for Site-Specific Portions of the Design Conceptual design information for site-specific portions of the design should be retained in the DCD, with appropriate discussion in the introduction section that a COL applicant is not required to conform with the conceptual design information.
- 7. Technical specifications '
Technical specifications should be retained in the DCD as Tier 2 l material. l
- 8. Miscellaneous i i
- a. Section numbering should be the same in the DCD as in the CDM and the SSAR. ;
1
- b. Guidelines for preparation of emergency procedures should be '
retained in the DCD.
- c. Information designated as safeguards-protected should not be con-tained in the DCD. Where safeguards information has been removed, the DCD should reference the appropriate sections of the SSAR. This information must also be submitted as part of a COL application.
- d. Large size drawings may be reduced to facilitate DCD preparation.
. _ _ _ _ _